The results are discussed, and the heats and heat treatments that are most resistant to fatigue damage under these leading and environmental conditions are identified.

Biaxial creep-fatigue data for Incoloy 800 and Type 316H stainless steel at elevated temperatures are presented. Tubular specimens were subjected to constant internal pressure and strain-controlled axial cycling with and without hold times in tension as well as in compression.

Aging of simulated nuclear waste glass by contact with a controlled-temperature, humid atmosphere results in the formation of a double hydration layer penetrating the glass, as well as the formation of minerals on the glass surface. The hydration process can be described by Arrhenius behavior between 120 and 240 C. Results suggest that simulated aging reactions are necessary for demonstrating that nuclear waste forms can meet projected Nuclear Regulatory Commission regulations.

An automated accountability system for special nuclear materials (SNM) is under development at Argonne National Laboratory-West. Phase I of the development effort has established the following basic features of the system: a unique file organization allows rapid updating or retrieval of the status of various SNM, based on "batch numbers," storage location, serial number, or other attributes. Access to the program is controlled by an interactive user interface that can be easily understood by operators who have had no prior background in electronic data processing. Extensive use of structured programming techniques make the software package easy to understand and to modify for specific applications. All routines are written in FORTRAN.

Large-scale efforts are in progress to develop advanced batteries for utility energy storage systems. Realization of the full benefits available from those systems requires development, not only of the batteries themselves, but also the ac/dc power converter, the bulk power interconnecting equipment, and the peripheral electric balance of plant equipment that integrate the battery/converter into a properly controlled and protected energy system. This study addresses these overall system aspects; although tailored to a 20-MW, 100-MWh lithium/sulfide battery system, the technology and concepts are applicable to any battery energy storage system.

This evaluation of radiation effects in silicate glasses caused by ionization is based on our own investigations, on material collected in our files (reports, articles, and notes), and on a computer literature search through recent issues of Physics Abstracts and Chemical Abstracts (and the apparently pertinent references which appeared). Some of the recent results, available heretofore only in internal correspondence, are presented in some detail. It is concluded that research into the behavior of silicate glasses generally will be required before the specific effects in the radioactive waste storage glasses can be properly understood and evaluated. Two particular neglected areas of investigation are targeted for immediate concern: a kinetic analysis of annealing data and the acquisition of data on effects of irradiation at controlled elevated temperatures.

This seventh Annual Report is a summary of some of the progress in scientific and engineering research and development carried on at Argonne National Laboratory during 1961. As is customary in this series, only those portions of the total program that have reached such a stage that they may be of general interest are recorded. Thus, a comparison with the Annual Reports for 1959 (ANL-6125) and for 1960 (ANL-6275) will reveal the description of a generally different set of scientific activities. A more detailed presentation of any work covered in this report or of the many ANL projects not mentioned may be obtained by perusing the various progress and topical reports issued by the Laboratory during 1961. A list of the publications in the scientific journals during 1961 by Argonne personnel has been given as an Appendix.

These annual meetings bring together contractors of the Division of Chemical Sciences in its basic research program on solar photochemical energy conversion to exchange information and to give interested government officials an opportunity to assess the current status of the program. This year's meeting was joined by 12 Canadian scientists with similar interests in solar photochemistry. This volume contains the program of the meeting, a list of attendees, the abstracts of 29 formal presentations and 36 posters, and a record of questions and answers following each presentation.

A series of experiments have been performed to test a calculational model for precipitation of NaH in sodium cold traps. The calculational model, called ACTMODEL, is a computer simulation that uses the system geometry and operating conditions as input to calculate a mass-transfer coefficient and the distribution of NaH in a cold trap. The ACTMODEL was tested using an analytical cold trap (ACT) that is simple and essentially one-dimensional. The ACT flow and temperature profile can be controlled at any desired condition. The ACT was analyzed destructively after each test to measure the actual NaH distribution. Excellent agreement was obtained between the ACTMODEL simulations and the experiments. Mass-transfer coefficients ranging upward from 6 x 10/sup -5/ m/s were measured in both packless and packed traps. As much as a fourfold increase in precipitation surface area was observed with increasing amount of NaH deposited.

This report documents the operation of a 28 in. long sodium heat pipe in the Heat Pipe Test Facility (HPTF) installed at Argonne National Laboratory. Experimental data were collected to simulate conditions prototypic of both a fluidized bed coal combustor application and a space environment application. Both sets of experiment data show good agreement with the heat pipe analytical model. The heat transfer performance of the heat pipe proved reliable over a substantial period of operation and over much thermal cycling. Additional testing of longer heat pipes under controlled laboratory conditions will be necessary to determine performance limitations and to complete the design code validation.

Operation of liquid-metal-cooled fast breeder reactors (LMFBRs) will result in production of various quantities of radioactive sodium waste. Two methods have been developed and tested on a small scale for converting this sodium waste to inert compounds suitable for disposal. The first method is direct oxidation of the sodium after dispersal in a silica matrix. The sodium is mixed with silica and oxidized in a rotary drum reactor. The product is suitable for making glass when other stabilizing compounds are added. The second method is reaction of elemental sodium with molten sodium hydroxide at 450 degrees C and subsequent injection of steam into the melt to convert the reaction products (Na2O and NaH) to additional sodium hydroxide. The reactions are smooth and easily controlled with little danger of run-away reactions. The end product is molten sodium hydroxide which can be cast into drums for further treatment or disposal. The advantages of these two methods over more conventional aqueous processes are the elimination of aqueous wastes and the elimination of minimization of gaseous effluents.

Many important additions and improvements have been made to Ptolemy since the previously-documented version of February 1976. An indication of this is that the list of keywords has been expanded by thirty. Collective-model inelastic excitement has been added. The computation of the transfer DWBA amplitudes has been significantly improved by the use of interpolation in the Ri +Ro variable. Elastic scattering and reactions involving identical particles may now be computed. Simultaneous optical model fits to several different elastic channels are possible. Significant changes to this manual are marked with a vertical bar in the left margin and should be carefully reviewed. In addition the contents of the manual have been extensively re-ordered.

The battery is a key element in the acceptance of electric vehicles, and R and D efforts are being undertaken to improve battery performance and lifetime. In this electric-vehicle battery program, controlled laboratory tests were conducted to evaluate the effects of selected factors on the performance and life of the EV-2300 lead-acid battery manufactured by Johnson Controls, Inc. These factors included simulated driving profiles with different levels of peak power demands for vehicle acceleration, long rest times after charge or discharge, and different methods of recharging. The performance and cycle life of a 12-module full-scale battery pack and its support system were also evaluated. This report summarizes the work carried out on this program from January 1985 through April 1986. This work involved tests of the battery pack and support system, statistical analysis of capacity and power data from earlier tests of six-cell modules, and post-test analysis of selected modules and cells.

Intergranular stress-corrosion crack (IGSCC) propagation rates were measured in three heats of sensitized Type 304 stainless steel (SS) as a function of sensitization in an environment of high-purity water with 8 ppm oxygen, using a fracture mechanics approach. Specimens were sensitized using controlled furnace heat treatments and the degree of sensitization was measured by the electrochemical potentiokinetic reactivation (EPR) method. Active loading tests were performed on standard specimens over a range of intensities. Crack lengths were determined by compilance measurements using in-situ high-temperature clip gage or LVDT methods, optical metallography on the side faces of the specimen, and fractography of the cracked surface after completion of the tests. The optical metallography measurements did not provide useful estimates of crack lengths, because large variations in IGSCC propagation across the thickness of the specimens occurred. The effects of the degree of sensitization on the IGSCC propagation rate are obscured by the data scatter. However, it seems clear that these variables do not lead to order-of-magnitude changes in the crack propagation rate.

In 1973, Argonne National Laboratory began consolidating and upgrading its plutonium-handling operations with the result that the research fuel-fabrication facility located in Building 350 was shut down and declared surplus. Sixteen of the twenty-three gloveboxes which comprised the system were disassembled and relocated for reuse or placed into controlled storage during 1974 but, due to funding constraints, full-scale decommissioning did not start until 1978. Since that time the fourteen remaining contaminated gloveboxes, including all internal and external equipment as well as the associated ventilation systems, have been assayed for radioactive content, dismantled, size reduced to fit acceptable packaging and sent to a US Department of Energy (DOE) transuranic retrievable-storage site or to a DOE low-level nuclear waste burial ground. The project which was completed in 1983, required 5 years to accomplish, 32 man years of effort, produced some 540 cubic meters (19,000 cubic ft) of radioactive waste of which 60% was TRU, and cost 2.4 million dollars.

Annual report for the superconductor program at Argonne National Laboratory discussing the group's activities and research.

The Unsaturated Test Method has been applied to study glass reaction under conditions that may be present at the potential Yucca Mountain site, currently under evaluation for storage of reprocessed high-level nuclear waste. The results from five separate sets of parametric experiments are presented wherein test parameters ranging from water contact volume to sensitization of metal in contact with the glass were examined. The most significant effect was observed when the volume of water, as controlled by the water inject volume and interval period, was such to allow exfoliation of reacted glass to occur. The extent of reaction was also influenced to a lesser extent by the degree of sensitization of the 304L stainless steel. For each experiment, the release of cations from the glass and alteration of the glass were examined. The major alteration product is a smectite clay that forms both from precipitation from solution and from in-situ alteration of the glass itself. It is this clay that undergoes exfoliation as water drips from the glass. A comparison is made between the results of the parametric experiments with those of static leach tests. In the static tests the rates of release become progressively reduced through 39 weeks while, …

Although the Dirac theory of the hydrogen atom was proposed more than half a century ago, extension of the theory and its practical applications to complex atomic spectra took decades to mature. Development of quantum electrodynamics (QED) in its modern form, advances in high precision experimental techniques, and invention of high-speed computers have made atomic spectroscopy one of the most accurate branches of physics today, both in theory and experiment. In addition to a long-standing need to identify line-spectra coming from far and near parts of the universe, necessities such as to test QED further and to provide reliable data for ions in tokamak plasmas require an understanding of the theory of relativistic atomic structure beyond the framework of the original Dirac theory. Twenty articles from the proceedings of the workshop are presented. Contributed papers are grouped into theoretical and experimental subjects and presented after the papers for the second (atomic structure calculations) and third (experiment) sessions of the Workshop. Alphabetical listing of the authors is presented in Appendix 1, program of the Workshop in Appendix 2, and the list of the participants in Appendix 3.

Calorimetric assay provides a precise, nondestructive method to determine sample plutonium content based on the heat emitted by decaying radionuclides. This measurement, in combination with a gamma-spectrometer analysis of sample isotopic content, yields the total sample plutonium mass. The technique is applicable to sealed containers and is essentially independent of sample matrix configuration and elemental composition. Conventional calorimeter designs employ large water-bath heat sinks and lack the portability needed by inspection personnel. The ANL air-chamber isothermal calorimeters are low-thermal-capacitance devices which eliminate the need for large constant-temperature heat sinks. These instruments are designed to use a feedback system that applies power to maintain the sample chamber at a constant electrical resistance and, therefore, at a constant temperature. The applied-power difference between a plutonium-containing sample and a blank determines the radioactive-decay power. The operating characteristics of a calorimeter designed for assaying mixed-oxide powders, fuel pellets, and plutonium-containing solutions are discussed. This device consists of the calorimeter, sample pre-heater, and a microprocessor-controlled data-acquisition system. The small-sample device weighs 18 kg and has a measurement cycle of 20 min, with a precision of 0.1% at 10 mW. A 100-min gamma-ray measurement gives the specific power with a precision of better than 1% for …

Most casting defects occur during initial pouring and therefore the design of the running system, which guides the metal from the ladle into the mold, is crucial. Traditionally, the running system and mold filling are designed by trial and error, which is tedious, time consuming, and expensive. The uncertainties that remain can be overcome by a computer simulation that demonstrates the actual process of mold filling and subsequent solidification. Computer simulation of various processes has become more and more common in recent years. The cost-effectiveness of making flawless castings has made the foundry worker more aware of the process of mold filling, identification of hot spots, etc. The macroscopic Casting Process Simulator (CaPS) software combines heat transfer and fluid flow aspects and can describe a variety of solidification aspects, including mold filling. CaPS is a two-dimensional time-dependent computer code involving a finite-volume formulation for the mass, momentum. and energy equations. CaPS has the following characteristics. CaPS uses the PATRAN geometric modeling package for constructing the geometry, generating a neutral file consisting of a list of named components, and post-processing of the simulation results; building the geometry independently of the mesh is a time-saving procedure. A structured mesh generator of structured …

Presented here are notes for a course in PL/I. They might serve as a guide to those who are developing a course, or as class notes for that course. They might be useful as a textbook independent of any course; as such a textbook, however, they are not self-contained because of the built-in assumption that they will supplement lectures and be accompanied by manuals. Very nearly the full language is taught here, with the emphasis on concepts rather than practical details. Discussion of I/O is avoided until roughly the midpoint of the course. The hoped-for consequence for students is an enhanced perception and understanding of the many concepts and their logical relationships. The dawning of the age of transportability for PL/I programs gives the user a reason, for the first time, to avoid convenient but illegal language.

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process.

A mathematical model for the instability of tube rows subjected to crossflow is examined. The theoretical model, based on the fluid-force data for a pitch-to-diameter ratio of 1.33, provides additional insight into the instability phenomenon. Tests are also conducted for three sets of tube rows. The effects of mass ratio, tube pitch, damping, detuning and finned tubes are investigated. Theoretical results and experimental data are in good agreement.

Annual report of the Argonne National Laboratory Chemical Engineering Division regarding studies of nuclear waste migration in geologic media. This report discusses research regarding nuclide migration and cesium absorption on limestone.